scholarly journals Space Nuclear Power - Reactor Coolant and Power Conversion System Concept - Approval of

2006 ◽  
Author(s):  
KH Donald
2017 ◽  
Vol 103 ◽  
pp. 74-84 ◽  
Author(s):  
Chenglong Wang ◽  
Jing Chen ◽  
Suizheng Qiu ◽  
Wenxi Tian ◽  
Dalin Zhang ◽  
...  

2019 ◽  
Vol 44 (2) ◽  
pp. 855-868 ◽  
Author(s):  
Zhiwen Dai ◽  
Chenglong Wang ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
...  

Author(s):  
Simiao Tang ◽  
Chenglong Wang ◽  
G. H. Su ◽  
Suizheng Qiu ◽  
Wenxi Tian

With the advantages of high reliability, high power density and long life, small nuclear power reactor has become one of the most excellent space power options in the space missions. TOPAZ-II is the most mature space nuclear power reactor based on thermionic conversion. In this paper, the thermo-physical and transport properties of NaK-78 and heat transfer correlations for liquid metals are implemented into the RELAP5 code. The modified RELAP5 has already been accessed to analyze the thermal-hydraulic characteristics of the space reactor cooled by NaK-78. A RELAP5 model including the core, TFEs, radiator, coolant loop and volume accumulator is developed. Temperature reactivity feedback, TFE emitter, TFE collector, moderator and the reactivity insertion effects of control drums and safety drums are modeled in the point reactor kinetics equations with six-group delayed neutrons. To V&V the integrated TOPAZ-II system model, the steady state is simulated and analyzed. The steady state calculated results are in good agreement with the designed values. On the basis of V&V, a hypothetical reactivity insertion accident is simulated and analyzed. During the accident, the automatic control system is assumed to be malfunctioned, 0.01$ positive reactivity is introduced for 500s and then control drums start to rotate inward. The maximum temperatures of fuel and emitter are below the melting temperature, respectively. The maximum temperature of coolant is 940K with 160K margin from boiling. With the rotating of control drums, the reactor reaches critical again.


Alloy Digest ◽  
1965 ◽  
Vol 14 (12) ◽  

Abstract Sanicro 71 is a nickel-base alloy having good resistance to stress-corrosion, oxidation and creep at elevated temperatures. It is recommended for nuclear power reactor heat exchanger tubes, aircraft turbojet engines and for equipment in the textile, plastic, and chemical industries. This datasheet provides information on composition, physical properties, hardness, elasticity, and tensile properties. It also includes information on high temperature performance and corrosion resistance as well as forming, heat treating, machining, joining, and surface treatment. Filing Code: Ni-108. Producer or source: Sandvik.


2001 ◽  
Author(s):  
K. Sakurai ◽  
H. S. Ko ◽  
K. Okamoto ◽  
H. Madarame

Abstract The characteristics of the supercritical fluids should be precisely investigated for the next generation nuclear power reactor, i.e., Super-critical water Cooled Reactor (SCR). There are few experiments for visual observation especially in forced convection, because of the difficulty of the experiment.


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